Alternatives and similar repositories for KOMODO:

Users that are interested in KOMODO are comparing it to the libraries listed below

• imronuke / ADPRES
  An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool
  ☆23Updated 4 years ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆42Updated 2 months ago
• NCSU-NCSG / THOR
  THOR is a radiation transport code for unstructured meshes.
  ☆13Updated 6 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆57Updated 2 months ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆40Updated 9 months ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆30Updated 2 months ago
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆103Updated last week
• openmsr / msre
  detailed cad model of the msre
  ☆36Updated last month
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆64Updated last year
• DrRyanMc / CompNucEng
  This repository holds codes from the book Computational Nuclear Engineering and Radiological Science with Python
  ☆15Updated 4 years ago
• FRENSIE / FRENSIE
  Framework for REsearch in Nuclear ScIence and Engineering
  ☆14Updated 3 years ago
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆52Updated 5 months ago
• arfc / moltres
  Repository for Moltres, a code for simulating Molten Salt Reactors
  ☆67Updated 3 weeks ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆56Updated last month
• aims-umich / pyMAISE
  Machine learning and artificial intelligence benchmarking library for nuclear engineering applications.
  ☆26Updated last week
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆23Updated 6 months ago
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆18Updated last year
• CEMeNT-PSAAP / MCDC
  MC/DC: Monte Carlo Dynamic Code
  ☆31Updated 2 weeks ago
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆33Updated 3 months ago
• SlaybaughLab / BART
  A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.
  ☆27Updated 3 years ago
• ezsolti / RFP
  ☆30Updated last month
• fusion-energy / neutronics-workshop
  A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…
  ☆141Updated this week
• mohamedlahdour / OpenNTP
  In this project we develop an OpenNTP package to solve the multi-group neutron transport equation.
  ☆11Updated 4 years ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆29Updated 7 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆51Updated last week
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆17Updated last year
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆40Updated this week
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆104Updated last month
• ERMETE-Lab / MP-OFELIA
  Openmc-FEnicsx for muLtiphysics tutorIAl
  ☆14Updated 8 months ago